System studies for ITER

R. L. Reid, Y. K.M. Peng, J. D. Galambos

Research output: Contribution to journalConference articlepeer-review

Abstract

The following system studies were performed for the International Thermonuclear Experimental Reactor (ITER) using the Tokamak Engineering Test Reactor Analysis (TETRA) systems code: (1) a study of inductive vs current drive options for ITER, which addresses the cost trade-off of providing increased plasma burn capability inductively by increasing the bore of the ohmic heating (OH) solenoid (resulting in a tokamak with a larger major radius) as opposed to providing plasma current drive via rf or neutral beam injection (NBI); (2) an inboard shield trade study, which addresses the trade-off of using tungsten or stainless steel shielding; and (3) a study of the impact of confinement scaling on ITER parameters, which addresses the sensitivity of various proposed energy confinement time scaling algorithms (Kaye-Goldston, Goldston, T10, JAERI, Rebut) on ITER ignition margin and cost.

Original languageEnglish
Pages (from-to)605-611
Number of pages7
JournalFusion Technology
Volume15
Issue number2 pt 2A
DOIs
StatePublished - 1989
EventProceedings of the Eighth Topical Meeting on the Technology of Fusion Energy - Salt Lake City, UT, USA
Duration: Oct 9 1988Oct 13 1988

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